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Stress relaxation in irradiated INCONEL X750 springs

Journal Article · · Transactions of the American Nuclear Society
OSTI ID:678154
;  [1]
  1. Argonne National Lab., Idaho Falls, ID (United States)

Because INCONEL X750 is used as a spring and bolting material in light water reactors, it is important to understand its stress relaxation behavior as a function of irradiation dose and aging temperature. This work reports the stress relaxation characteristics of INCONEL X750 irradiated at 375 to 415C to doses up to 20 dpa and thermally aged at 371 C for 6525 days. These measurements are an extension of stress relaxation measurements reported in Refs. 1 and 2.

OSTI ID:
678154
Report Number(s):
CONF-990605--
Journal Information:
Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 80; ISSN 0003-018X; ISSN TANSAO
Country of Publication:
United States
Language:
English

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